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Study of the Transients of Loss of Coolant Accident in an Installation Pressurized with the RELAP5/mod3.2 System Code

机译:用RETAP5 / MOD3.2系统代码加压的安装中冷却液事故损失瞬变的研究

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This study consists of the simulation of a number of thermal-hydraulic transients, like the LOCA (Loss Of Coolant Accident), that can occur during the operation of a highly pressurized test loop, under saturation conditions. The loop is intended mainly for the tests of irradiations of nuclear fuel under high pressure and high temperature conditions (155 bars, 300 deg C). Three test sections (IPS), provided each one with an assembly with nine combustible bars, are conceived for this purpose. The primary cooling system is composed of a heat exchanger, a pressurizer and three test sections, in addition to the connecting pipe and sets of valves for regulate the flows. The RELAP5 code (Reactor Excursion and Leak Analysis Program) is a system code, broadly known, conceived for the simulation of the thermal-hydraulic behaviour of nuclear and non-nuclear installations. Our work, concerns two transients of loss of coolant accident in the primary cooling system. There is a whole spectrum of possible breaks of the primary cooling system, beginning with those which are sufficiently small so that the escapes are compensated by the flow of load of the volumetric and chemical checking loop, until the complete break of a principal pipe of the primary cooling system, accompanied by complete separation and double ended guillotine pipe break. This last rupture can be supposed to occur on the level of: the hot branch, between the section of tests and the heat exchanger, the intermediate branch, between the heat exchanger and the primary pump, and finally, the cold branch, between the pump and the test sections, at the return towards the core of the test sections (I.P.S). The spectrum of this type of breaks and their various localizations, deserve to be studied, because the physical and mechanical phenomena as well as the behaviour of the systems of safeguard (safety and control) vary from one case to another. In this article, we present the principal results of the analysis of two LOCA accidents simulated with RELAP5/MOD3.2 code.
机译:本研究由许多热工水力瞬变的,如LOCA(损失失水事故)的模拟,能够在高度加压的测试回路的操作过程中发生,饱和的条件下。该回路主要用于核燃料的照射的在高压和高温条件下(155巴,300℃)测试。三个测试部分(IPS),设置有装配有九个可燃杆的每一个,都被设想用于此目的。初级冷却系统是由热交换器,加压器和三个测试段,除了阀的连接管和集调节流动。该RELAP5代码(反应堆游览和泄漏分析程序)是一个系统的代码,广为人知,设想用于核与非核设施的热工水力行为的模拟。我们的工作,涉及的主要冷却系统失水事故的两个瞬时电压。有主冷却系统的可能断裂的整个光谱,与那些有足够小,使得逃逸由体积和化学检查环的负载的流量补偿开始,直到的主配管的完全断裂初级冷却系统,伴随着完全分离和双端铡管道破裂。这最后破裂可以假定上的电平发生:在热分支,测试的部分和热交换器,中间分支之间,热交换器和主泵,最后,将冷分支之间,所述泵之间与测试的部分,在朝向测试段(IPS)的芯中的回报。这种类型的场所及它们的各种本地化的的光谱,值得研究的,因为物理和机械现象以及保障(安全和控制)的系统的行为变化从一个情况到另一。在这篇文章中,我们提出用RELAP5 / MOD3.2代码模拟2起LOCA事故分析的主要结果。

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